From the Phenix irradiation end to the analytical results: PROFIL R target destructive characterization

Ferlay, Gilles; Dancausse, J.P.; Lévêque, Pierre; Eymard, S.; Carre, D.; Bienvenu, Philippe; Guy, Christophe; Gautier, Céline; Isnard, Hélène; Goutelard, F.; Bourdot, P.; Boucher, L.; Bonnerot, J.M.

doi:10.1088/1757-899x/9/1/012021

Cited by 5 publications

(4 citation statements)

References 4 publications

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“…Several developments have been conducted in a high-activity laboratory to optimize the powder recovery procedure with the aim to minimize the impact of the steel in the final dissolution solution. 5 The first 235 U container was opened in 2009. During the opening step, close to 30% of the steel (around 45 mg) was dissolved simultaneously with the powder.…”

Section: Reagents Materials and Samplementioning

confidence: 99%

“…The samples, enclosed in small containers, are different types of enriched actinides (11 types including 9 containers of 235 U) and fission products (33 types). 5,6 Enriched actinides and fission products, namely transmutation target samples, were irradiated in the Ph enix French fast neutron nuclear reactor to get new insights into basic neutronic data such as cross sections and reaction rates. Determining these data requires precise, accurate and complete isotopic measurements of samples before and after irradiation.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Simultaneous uranium/plutonium separation and direct isotope ratio measurements by using CO2 as the gas in a collision/reaction cell based MC-ICPMS

Gourgiotis

Granet

Isnard

et al. 2010

J. Anal. At. Spectrom.

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Section: Reagents Materials and Samplementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Simultaneous uranium/plutonium separation and direct isotope ratio measurements by using CO2 as the gas in a collision/reaction cell based MC-ICPMS

Gourgiotis

Granet

Isnard

et al. 2010

J. Anal. At. Spectrom.

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“…After irradiation, the container was opened in a hot cell to remove all the powder. The opening aimed at ensuring a total extraction of the powder and at avoiding any presence of the steel container (Ferlay et al, 2010). After irradiation around 400 g of 151 Sm had been produced by the nuclear reactions.…”

Section: Preparation Of the 151 Sm Solutionmentioning

confidence: 99%

Results of the EURAMET.RI(II)- S7.Sm-151 supplementary comparison (EURAMET Project 1292)

Bé¹,

Cassette²,

Brondeau³

et al. 2015

Metrologia

Self Cite

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An international comparison of the activity standardisation of the relatively long-lived gamma-ray emitter 151 Sm has been recently completed. A total of six laboratories measured a solution prepared by CEA/LNHB and CEA/LANIE. Aliquots of the master solution were standardized in terms of activity per mass unit by participant laboratories using 2 different techniques. The results of the comparison can be used as the basis for establishing equivalence among the laboratories. The activity measurements of this comparison are part of the joint research project "Metrology for Radioactive Waste Management" of the European Metrology Research Programme (EMRP). One aim of this project is a new determination of the 151 Sm half-life. 1.

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“…After irradiation and a cooling period of about 3 years, the container was opened in hot cell facilities (CEA Cadarache, France) and the powder was dissolved with 14N HNO 3 . 41 Relative to the high activity of this solution, only 100 ml was supplied in the Isotopic and Elementary Analysis Laboratory (LANIE, CEA Saclay, France) for elementary and isotopic measurements. Concentrations of this solution in Europium, Gadolinium and Samarium were respectively around 650, 48 and 0.4 mg mL À1 .…”

Section: Irradiated Fuel Samplementioning

confidence: 99%

Sm isotope composition and Sm/Eu ratio determination in an irradiated 153Eu sample by ion exchange chromatography-quadrupole inductively coupled plasma mass spectrometry combined with double spike isotope dilution technique

Bourgeois

Isnard

Gourgiotis

et al. 2011

J. Anal. At. Spectrom.

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Within the framework of the research undertaken by the French Atomic Energy Commission on transmutation of long-lived radionuclides, targets of highly enriched actinides and fission products were irradiated in the fast neutron reactor Ph enix. Precise and accurate measurements of the isotopic and elemental composition of the enriched elements are therefore required. In order to obtain the uncertainties of several permil and to reduce handling time and exposure to analyst on radioactive material, the on-line coupling of ion exchange chromatography with quadrupole inductively coupled plasma mass spectrometry has been associated with the technique of the double spike isotope dilution. We present in this paper the results obtained on an irradiated sample of Europium oxide powder (enriched at 99.13% in 153 Eu). After irradiation of around 5 mg of Eu 2 O 3 powder the theoretical calculations predict the formation of several micrograms of gadolinium and samarium isotopes. In relation to the very high activity of the sample after irradiation and the very low quantity of Sm formed, the on-line ion exchange chromatography separation of Gd, Sm and Eu before Sm isotope ratio measurements has been developed for the quantification of the 152 Sm/ 153 Eu ratio. These on-line measurements were associated with the double spike isotope dilution technique after calibration of a 147 Sm/ 151 Eu spike solution. The external reproducibility of Sm isotopic ratios was determined to be around 0.5% (2s) resulting in a final uncertainty on the 152 Sm/ 153 Eu ratio of around 1% (2s). These on-line measurements present therefore a robust and high-throughput alternative to the thermal-ionisation mass spectrometry technique used so far in combination with off-line chromatographic separation, particularly in nuclear applications where characterisation of high activity sample solutions is required. 153 a Commissariat a l'Energie Atomique, DEN/DPC/SECR/LANIE, bât 391,

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From the Phenix irradiation end to the analytical results: PROFIL R target destructive characterization

Cited by 5 publications

References 4 publications

Simultaneous uranium/plutonium separation and direct isotope ratio measurements by using CO2 as the gas in a collision/reaction cell based MC-ICPMS

Simultaneous uranium/plutonium separation and direct isotope ratio measurements by using CO2 as the gas in a collision/reaction cell based MC-ICPMS

Results of the EURAMET.RI(II)- S7.Sm-151 supplementary comparison (EURAMET Project 1292)

Sm isotope composition and Sm/Eu ratio determination in an irradiated 153Eu sample by ion exchange chromatography-quadrupole inductively coupled plasma mass spectrometry combined with double spike isotope dilution technique

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